Results 91 to 100 of about 56,822 (209)
Determining Reactor Neutrino Flux
, 2012 Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes.
Cao, Jun
core +1 more source
, 1980 CALIPSOS is a steady-state three-dimensional flow distribution code which predicts the fluid dynamics and heat transfer interactions of the secondary two-phase flow in a steam generator. The mathematical formulation is sufficiently general to accommodate two fluid models described by separate gas and liquid momentum equations.
R. Fanselau +3 more
openaire +2 more sources
Educational Activities to Help Transferring Knowledge in Nuclear: The Seminars of Spanish Young Generation in Nuclear (Jóvenes Nucleares) [PDF]
, 2011 From its creation, Spanish Young Generation in Nuclear (Jóvenes Nucleares, JJNN), a non-profit organization that depends on the Spanish Nuclear Society (SNE), has as an important scope to help transferring the knowledge between those generations in the ...
Alvarez, A. +4 more
core +1 more source
PWR decontamination feasibility study [PDF]
, 1978 The decontamination work which has been accomplished is reviewed and it is concluded that it is worthwhile to investigate further four methods for decontamination for future demonstration. These are: dilute chemical; single stage strong chemical; redox processes; and redox/chemical in combination. Laboratory work is recommended to define the agents and
openaire +2 more sources
Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases [PDF]
, 2011 The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications.
Avramova, Maria, Cuervo Gómez, Diana
core +1 more source
Dissolution Behavior of Simulated Co Colloid in Oxidation Operation Process during Shutdown of PWRs
Yuanzineng kexue jishu, 2022 58Co and 60Co are the primary radionuclides and contributors to collective dose of PWRs, which may exist in ionic, particle and colloidal state in the primary loop. The pore diameter of the most advanced filter used in chemical and volume control system
LI Fuhai;LIANG Weijiang;FANG Jun;LIN Genxian;LI Xinmin;SUN Yun
doaj
ROSA/LSTF test on nitrogen gas behavior during reflux condensation in PWR and RELAP5 code analyses
Mechanical Engineering Journal, 2018 We conducted an experiment to clarify nitrogen gas behavior at low pressures during reflux condensation in a pressurized water reactor (PWR) with the rig of safety assessment/large scale test facility (ROSA/LSTF) at Japan Atomic Energy Agency.
Takeshi TAKEDA, Iwao OHTSU
doaj +1 more source
User's manual for COPTRAN, a method of optimum communication system design [PDF]
User manual for COPTRAN /communication system optimization program ...
Brinkman, K. L. +2 more
core +1 more source
Comparison of Hexagonal and Square Fuel Pin Arrangement with UN-PuN Fuel in PWR
Computational and Experimental Research in Materials and Renewable EnergyIndonesia is experiencing an increasing demand for electrical energy, which can be met through alternative sources such as nuclear energy generated in nuclear reactors at Nuclear Power Plants (NPPs).
Muhammad Syu’bi Alwi +3 more
doaj +1 more source
Indonesian Journal of Applied PhysicsZircaloy-4 (Zr-4) is used as a fuel cladding material in Pressurized Water Reactor (PWR). Zr-4 as a cladding material works in extreme conditions in pressurized water up to 150 atm at 325 ˚C.
Fajar Al Afghani, Anawati Anawati
doaj +1 more source